ML24289A233
| ML24289A233 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/25/2024 |
| From: | Byrd T Plant Licensing Branch IV |
| To: | Dent J Nebraska Public Power District (NPPD) |
| Wengert T, NRR/DORL/LPLIV, 415-4037 | |
| References | |
| EPID L-2024-LLA-0015 | |
| Download: ML24289A233 (1) | |
Text
November 25, 2024 John Dent, Jr.
Executive Vice President and Chief Nuclear Officer Nebraska Public Power District 72676 648A Avenue P.O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - ISSUANCE OF AMENDMENT NO. 279 REGARDING REVISION TO TS TABLE 3.3.5.1-1, EMERGENCY CORE COOLING SYSTEM INSTRUMENTATION, FUNCTION 3.f, HIGH PRESSURE COOLANT INJECTION PUMP DISCHARGE FLOW - LOW (BYPASS)
Dear John Dent,
Jr.:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 279 to Renewed Facility Operating License No. DPR-46 for Cooper Nuclear Station (Cooper). The amendment consists of changes to the technical specifications (TSs) in response to your application dated February 16, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24047A273), as supplemented by letter dated July 24, 2024 (ML24207A107).
The amendment revises the allowable value for Cooper TS 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation, table 3.3.5.1-1, Emergency Core Cooling System Instrumentation, function 3.f, High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass), from greater than or equal to () 490 gallons per minute (gpm) to 523 gpm. This change to the TS table is due to a planned replacement of the flow-indicating switch with a different model.
J. Dent, Jr.
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Thomas J. Byrd, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosures:
- 1. Amendment No. 279 to DPR-46
- 2. Safety Evaluation cc: Listserv
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 279 Renewed License No. DPR-46
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated February 16, 2024, as supplemented by letter dated July 24, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-46 is hereby amended to read as follows:
(1)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 279, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance and shall be implemented by April 30, 2025, to support scheduled system maintenance window.
FOR THE NUCLEAR REGULATORY COMMISSION Tony T. Nakanishi, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. DPR-46 and the Technical Specifications Date of Issuance: November 25, 2024 Tony T.
Nakanishi Digitally signed by Tony T. Nakanishi Date: 2024.11.25 13:13:40 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 279 RENEWED FACILITY OPERATING LICENSE NO. DPR-46 COOPER NUCLEAR STATION DOCKET NO. 50-298 Replace the following pages of Renewed Facility Operating License No. DPR-46 and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 3.3-40 3.3-40
Amendment No. 279 (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2419 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 279, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: Cooper Nuclear Station Safeguards Plan, submitted by letter dated May 17, 2006.
NPPD shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NPPD CSP was approved by License Amendment No. 238 as supplemented by changes approved by License Amendments 244 and 249.
(4) Fire Protection NPPD shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the license amendment request dated April 24, 2012 (and supplements dated July 12, 2012, January 14, 2013, February 12, 2013, March 13, 2013, June 13, 2013, December 12, 2013, January 17, 2014, February 18, 2014, and April 11, 2014), and as approved in the safety evaluation dated April 29, 2014.
Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if
FUNCTION 3.
HPCI System (continued) f.
High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass)
- 4. Automatic Depressurization System (ADS) Trip System A a.
- Low Low Low (Level 1)
- b. Automatic Depressurization System Initiation Timer
- c.
- Low (Level 3)
(Confirmatory)
- d. Core Spray Pump Discharge Pressure - High ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION 2
2 CONDITIONS REFERENCED FROM REQUIRED SURVEILLANCE ACTION A.1 REQUIREMENTS E
F G
F G
SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)
SR 3.3.5.1.5 SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)
SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)
SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 ALLOWABLE VALUE
- 523 gpm
- 2: -113 inches N 109 seconds
- 3 inches
- 108 psig and N 160 psig continued (c) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (L TSP) at the completion of the surveillance, otherwise, the channel shall be declared inoperable. Setpoints more conservative than the L TSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The Limiting Trip Setpoint and the methodologies used to determine the as found and the as-left tolerances are specified in the Technical Requirements Manual.
(f)
With reactor steam dome pressure >150 psig.
Cooper 3.3-40 Amendment No. 279
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 279 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-46 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
1.0 INTRODUCTION
By letter dated February 16, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24047A273), as supplemented by letter dated July 24, 2024 (ML24207A107), Nebraska Public Power District (the licensee) submitted a license amendment request (LAR) to the U.S. Nuclear Regulatory Commission (NRC, the Commission) for the Cooper Nuclear Station (Cooper). The proposed amendment would revise the allowable value (AV) for Cooper Technical Specification (TS) 3.3.5.1, Emergency Core Cooling System (ECCS)
Instrumentation, table 3.3.5.1-1, Emergency Core Cooling System Instrumentation, function 3.f, High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass), from greater than or equal to () 490 gallons per minute (gpm) to 523 gpm. The proposed change to the TS table is due to a planned replacement of the flow-indicating switch with a different model.
The supplemental letter dated July 24, 2024, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on April 16, 2024 (89 FR 26947).
2.0 REGULATORY EVALUATION
2.1
System Description
The licensee provided a description of the Cooper high pressure coolant injection (HPCI) system in section 2.1, System Design and Operation, of its LAR. In section 2.3 of the LAR, the licensee provided the reason for the proposed TS change. Specifically, the licensee is planning to replace a detector used in the HPCI system with a different model.
2.2 Proposed Change The proposed change would revise the AV for Cooper TS table 3.3.5.1-1, function 3.f from 490 gpm to 523 gpm.
2.2 Regulatory Requirements The Commissions regulatory requirements related to the content of TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) 50.36, Technical specifications, which requires, in part, that the TSs include items in the following categories: (1) safety limits (SLs), limiting safety system settings (LSSSs), and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. The regulation at 10 CFR 50.36(c)(1)(ii)(A) states, in part:
Limiting safety system settings for nuclear reactors are settings for automatic protective devices related to those variables having significant safety functions.
If, during operation, it is determined that the automatic safety system does not function as required, the licensee shall take appropriate action, which may include shutting down the reactor.
The regulation at 10 CFR 50.36(c)(3) states that SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
3.0 TECHNICAL EVALUATION
3.1 Technical Specifications TSs are required by 10 CFR 50.36 to include LSSSs for variables that have settings for automatic protective devices related to those variables having significant safety functions. The analytical limit (AL) is the limit of the process variable at which a safety action is initiated, as established by the safety analysis, to ensure that a SL is not exceeded. Any automatic protective action that occurs on reaching the AL therefore ensures that the SL is not exceeded.
However, in practice, the actual settings for automatic protection channels must be chosen to be more conservative than the AL to account for instrument loop uncertainties related to the setting at which the automatic protective action would occur.
The AV specified in Cooper TS table 3.3.5.1-1 is used to assess the operability of the component during SRs. That is, a channel is operable if the trip setpoint is found to not exceed the AV. As such, the AV differs from the trip setpoint by an amount primarily equal to the expected instrument loop uncertainties, such as drift, during the surveillance interval. In this manner, the actual setting of the device will still meet the LSSS definition and ensure that automatic system operation occurs as long as the device has not drifted beyond that expected during the surveillance interval.
The NRC staff reviewed the licensees justifications and explanations for the proposed change to the AV in Cooper TS table 3.3.5.1-1, function 3.f. Specifically, the staff reviewed the setpoint calculation in the LAR and reviewed supporting documents via audit. As a result of the audit, the setpoint calculation was revised to reflect the correct usage of drift uncertainty. However, this revision did not affect the AV proposed in the LAR. Based on its review, the staff finds that the setpoint calculation, as revised, supports the proposed change to the AV for Cooper TS table 3.3.5.1-1, function 3.f from 490 gpm to 523 gpm.
3.2 NRC Staff Determination The NRC staff determined that the TS, as modified, will continue to meet 10 CFR 50.36(c)(1) because the TS will continue to contain appropriate settings for automatic protective devices related to those variables having significant safety functions and will continue to require the licensee to take appropriate action when it is determined that the automatic safety system does not function as required. The staff also determined that the TS, as modified, will continue to meet 10 CFR 50.36(c)(3) because the SRs will continue to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. Therefore, the staff finds that the proposed change is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Nebraska State official was notified of the proposed issuance of the amendment on August 16, 2024. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, published in the Federal Register on April 16, 2024 (89 FR 26947), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: J. Ashcraft, NRR M. Hamm, NRR S. Sun, NRR Date: November 25, 2024
- concurrence via email NRR-058 OFFICE NRR/DORL/LPL4/PM* NRR/DORL/LPL4/LA*
NRR/DSS/STSB/BC*
NRR/DSS/SNSB/BC*
NAME TByrd PBlechman SMehta PSahd DATE 10/15/2024 10/21/2024 10/31/2024 10/23/2024 OFFICE NRR/DEX/EICB/BC*
OGC - NLO*
NRR/DORL/LPL4/BC* NRR/DORL/LPL4/PM*
NAME FSacko(NCarte for)
JWatchutka TNakanishi TByrd DATE 10/24/2024 11/22/2024 11/25/2024 11/25/2024